ML17059A936
| ML17059A936 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 09/11/1995 |
| From: | NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML17059A935 | List: |
| References | |
| NUDOCS 9509140224 | |
| Download: ML17059A936 (10) | |
Text
1P,R REGII "o
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UNITED STATES NUCLEAR REGULATORY COlltIMlsslObl WASHINGTON, D.C. 20555-0001 SAF FV lUAT 0 V 1HE OFFICE OF NUC[.VA. RE
.(0"..:G~lf~~I0 RELATED TG AM NDMENT NO. 6 TO FACILITY OPERATIN(: LICFNSE NO. HPF-69 NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT NUCLEAR STATION UNIT 2 DOCKET NO. 50-410 1.1
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By letter dated January 6,
1995, the Niagara Mohawk Power Corporation (the licensee) submitted a request for changes to the Nine Mile Point Nuclear Station, Unit 2, (NMP-2) Technical Specifications (TSs).
The requested changes would incorporate Limiting Condition for Operation (LCO) 3.3.3.1 from NUREG-1433, "Standard Technical Specifications General Electric Plants BWR/4,."
dated September 1992, into TS 3/4.3.7.5, Accident Monitoring Instrumentation
'nd make associated changes in TS 3/4.4.2, Safety Relief Valves.
2.0 BACKG OUND The purpose of the post-accident moni coring (PAH) instrumentation is to display variables that provide information required by the control room operators during accident situations.
'This information provides the necessary support for the operator to take the manual actions required for safety systems to accomplish their safety functions for design basis accidents (DBAs).
The operability of the PAN instrumeritation ensures that sufficient information is available on selected parameters for the operator to monitor and to assess unit status and behavior following an accident.
The following evaluation addresses the operability requirements and the associated required actions.,
- 3. 0 EVALUATION Incorporation of the Standard Technical Specifications (STSs)
LCO 3.3.3.1 would:
- a. 'elete the column titled "Minimum Channels Operable" from TS Table 3.3.7.5-1 and the column titled "Applicable Operational Conditions" from TS Tables 3.3.7.5-1 and C.3.7.5-1.
b.
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Revise the action statements in TS Table 3.3.7.5-1 associated with inoperability of instrumentation for the PAH parameters.
Revise LCO 3.3.7.5 to indicate that PAM is required to be operable in Operational Conditions 1 and 2.
Revise LCQ 3.3.7.5 to include an exception from TS 3.0.4.
9509140224 950911 PDR ADOCK 05000010 P
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Revise the "Required Number of Channels" encl thG name of the primary containment isolation valve (PCIV) position instrumentation in TS Tables 3.3.7.5-1 and 4.3.7.5-1.
f.
Delete the operability and surveillance requirements from TS Tables 3.3.7-5.1 and 4.3.7.5-1 for safety relief valve position, residual heat removal (RHR) heat exchanger service water radiation, refuel platform area radiation, and neutron flux monitoring instrumentation.
g.
Revise TS 3/4.4.2 to reference the safety relief valve testing performed under TS 4.0.5, revise LCO 3.4.2 to remove the operability requirements and action statements associated with safety relief valve acoustic monitors, and delete the surveillance requirements associated with safety relief valve acoustic monitors.
3.1 Required Channels The licensee proposed
'a revision to TS Table 3.3.7.5-1 to the format presented in STS Table 3.3.3. 1-1 by deleting the column titled "Hinimum Channels Operable."
LCO 3.3.3. 1 of the STS requires two operable channels for most PAH functions.
Two operable channels ensure that no single failure prevents the operator from getting information necessary for determining the safety status of the unit, and bringing the unit. to a safe condition following an accident.
Consistent with SYS Table 3.3.3. 1-1, the licensee has proposed that two channels for each parameter be provided as specified in TS Table 3.3.7.5-1, and is, therofore, acceptable.
3.2 Applicable Operational Conditions The licensee proposed a revision to TS Tables 3.3.7.5-1 and 4.3.7.5-1 to the format presented in STS Table 3.3.3.-1-1 by deleting the column titled "Applicable Operational Conditions."
LCO 3.3.3.1 of the STS includes the applicability requirements for PAH instrumentation.
Consistent with STS LCO 3.3.3.1 and STS Table 3.3.3.1-1, the licensee has proposed that the applicability requirements be included in LCO 3.3.7.5, and is, therefore, acceptable.
The current TS Tables 3.3.7.5-1 and 4.3.7.5-1 require reactor water level, suppression pool water level, and drywell high range radiation instrumentation to be operable in Operational Conditions 1, 2, and 3.
The licensee has proposed the deletion of the requirement to have. these instruments operable in Operational Condition 3, Hot Shutdown.
PAH variables are related to diagnosis and preplanned actions required to mitigate DBAs.
DBAs are assumed to occur during Operational Conditions 1 and 2.
Therefore, these instruments are not required to be operational in Operational Condition 3.
This is consistent with STS LCO 3.3.3. 1 which requires PAH instrumentation to be operational in Operational Conditions 1 and 2.
Therefore, the deletion of the requiremont 1
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for reactor water level, suppression poo: wai,er leve>,
and dry.all high range radiation instrumentation to be operable in Operational Condition 3 is acceptable.
3.3 Exception to the Provisions of TS 3.0.4 The licensee has proposed a revision to LCO 3.3.7.5 to include an exception from the provisions of TS 3.0.4.
TS 3.0.4 prohibits entry into operational conditions unless the conditions for LCOs are met without reliance on provisions contained in action statements.
The provisions of TS 3.0.4 are not applicable for PAM instrumentation because the PAN instrumentation restoration requirements provide adequate time to restore inoperable channels without placing undue pressure on plant personnel.
STS LCO 3.3.3. 1 includes a similar exception from the provisions of TS 3.0.4.
The proposed exception from the provisions of TS 3.0.4 is consistent with the STS, and is, therefore, acceptable.
3.4 Primary Containment Isolation Valves The licensee has proposed a revision to the "Required Number of Channels" and:.
the name of the PCIV instrumentation in TS Tables 3.3.7.5-1 and 4.3.7.5-1.
BASES 3.3.3. 1 of the STS states that for PCIV position, the important information is the isolation status of the containment penetration.
For containment penetrations with only one active PCIV having control room indication, only a single channel of valve position information is requi) ed to be operable.
To assure correct implementation of the required actions the licensee has proposed to revise the name from "Primary Containment Isolation Valve Position Indication" to "Penetration Flow Path Primary Containment Isolation Valve Position Indication" and revise the "Required Number of Channels" from I channel per PCIV to 2 channels per penetration.
A footnote has also been proposed to clarify that only one instrument channel is required for penetrations with only one active PCIV.
The licensee's proposal is consistent with STS Bases 3.3.3. 1, and is, therefore, acceptable.
3.5 RHR Heat Exchanger Service Water Radiation RHR heat exchanger service water radiation is not a Regulatory Guide (RG) 1.97, "Instrumentation for Light Mater Cooled Nuclear Power Plants to Assess Plant Conditions During and Following an Accident", variable and is not considered appropriate instrumentation for incorporation in the PAM TSs.
Therefore, RHR heat exchanger service water radiation monitoring instrumentation is being deleted from TS Tables 3.3.7.5-1 and 4.3.7.5-1.
The deletion of RHR heat exchanger service water radiation monitoring instrumentation from TS Tables 3.3.7.5-1 and 3.3.7.5-1 is acceptable.
3.6 Refuel Platform Area Radiation Refuel platform area radiation monitoring is not a
RG 1.97 variable, and is not cons'idered appropriate instrumentation for incorporation in the PAN TSs.
Therefore, refuel platform area radiation monitoring instrumentation is being
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deleted from TS Tables 3.3.7.5-1 arid 4.3.7.'-1.
The deletion of refuel platform area radiation monitoring instrumentation from l'S Tables 3.3.7.6-1 and 4.3.7.5-1 is acceptable.
3.7 Neutron Flux Neutron flux monitoring instrumentation is Type B as defined in RG 1.97 and conforms to the design and function criteria of NEDO-31558A previously approved by the staff.
This instrumentation is not considered appropriate for incorporation in the PAM TSs.
Therefore, neutron flux monitoring instrumentation is being deleted from TS Tables 3.3.7.5-1 and 4.3.7.5-1.
The deletion of neutron flux monitoring instrumentation from TS Tables 3.3.7.5-1 and 4.3.7.5-1 is acceptable.
3.8 Safety Relief Valve Position Safety relief valve position monitoring is Type D, Category 2 as defined in RG 1.97.
Type D, Category 2 instrumentation is not considered appropriate instrumentation for incorporation in the PAN TSs.
Therefore, safety relief valve position monitoring instrumentation is being deleted from TS Tables 3.3.7.5-1 and 4.3.7.5-1.
The deletion of safety relief valve position monitoring instrumentation from TS Tables 3.3.7.5-1 and 4.3.7.5-1 is acceptable.
TS 3/4.4.2 includes operability and surveillance requirements for safety relief valves.
Consistent with the deletion of safety relief valve position instrumentation from TS Tables 3.3.7.5-1 and 4.3.7.5-1, the licensee has proposed the revision of TS 3/4.4.2 to delete operability and surveillance reouirements for safety relief valve acoustic monitors.
The licensee has proposed that LCO 3.4.2 be revised to delete operability requirements and action statements associated with safety relief valve acoustic monitors.
The licensee has also proposed that a new surveillance requirement be added to TS 3/4.4.2 which would clarify that all required surveillance for the safety function of the safety relief valves are accomplished under TS 4.0.5.
Since safety relief valve position information is not required, the proposed revisions to TS 3/4.4.2 are acceptable.
Based on our review of the proposed amendment, the NRC staff concludes that the proposed changes to the PAN instrumentation operability requirements for the Nine Nile Point Nuclear Station, Unit No. 2, TS conform to the STS and their bases and the guidelines of RG 1.97.
The staff determined that the proposed TS changes provide appropriate LCO and action statements for the PN instrumentation, and are, therefore, acceptable.
4.0 STATE CONSULTAT ON In accordance with the Commission's regulations, the New York State official was notified of the proposed issuance of the amendment.
The State official had no comments.
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5.0 NOH T
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) Rf' The amendment changes a requirement with respect to installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20 and changes surveillance requirements.
The NRC staff has determined that the amendment involves no significant increase in the amounts, and no significant change in the types, of any effluents that may be. released
- offsite, and that there is no significant increase in individual or cumulative occupational radiation exposure.
The Commission has previously issued a
proposed finding that the amendment involves no significant hazards consideration, and there has been no public comment on such finding (60 FR 8748).
Accordingly, the amendment meets the eligibilitycriteria for categorical exclusion set forth in 10 CFR 51.22(c)(9).
Pursuant to 10 CFR 51.22(b) no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendment.
- 6. 0 CONCLUSION The Commission has concluded, based on the considerations discussed
- above, that:
(1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed
- manner, (2) such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the public.
Principal Contributors:
B. Marcus Date:
September ll, 1995
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